ML12356A456

301 Final Administrative Documents

ML12356A456
Person / Time
Site:	Catawba
Issue date:	12/17/2012
From:	Division of Reactor Safety II
To:	Duke Energy Corp
References
ES-201, ES-201-1 50-413/12-301, 50-414/12-301
Download: ML12356A456 (52)

Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Catawba Date of Examination: 9/4 - 9/12/12 Facility NRC Examinations Developed by:

Written / Operating Test Written / Operating Test Chief Target Task Description (Reference) Examiners Date*

Initials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) PGC

-120 2. NRC examiners and facility contact assigned (C.1.d; C.2.e) PGC

-120 3. Facility contact briefed on security and other requirements (C.2.c) PGC

-120 4. Corporate notification letter sent (C.2.d) PGC

[-90] [5. Reference material due (C.1.e; C.3.c; Attachment 2)] PGC

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, PGC as applicable (C.1.e and f; C.3.d)

{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility PGC licensee (C.2.h; C.3.e)}

{-45} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, PGC ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398's) due (C.1.l; C.2.g; ES-202) PGC

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES- PGC 202)

-14 11. Examination approved by NRC supervisor for facility licensee review PGC (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) PGC

-7 13. Written examinations and operating tests approved by NRC supervisor PGC (C.2.i; C.3.h)

-7 14. Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent PGC (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed PGC with facility licensee (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to PGC NRC examiners (C.3.i)

• Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

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Form ES-201-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) ofg,Zbit as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee, will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of A . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations

, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

ES-20 I 0

Examination Security Agreement Form ES-201-3

1. Pre-Examination I acknowledge that I have acuired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of Ras of the date of my signature. I agree that I will not knowingly divulge any information about f these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio n, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination instruct, evaluate, or provide performance feedback to those applicants who were administered administration, I did not these licensing examinations, except as specifically noted below and authorized by the NRC.

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hF ES-201, Page 27 of 28

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E-o1 Examinatio n Securit y Agreem

1. en t Pre-Examlna tlon Form ES

-201-3 I acknowledge that I have acquired sp of my signature. I ecialized knowledge agree that I. will not about the know the NRC chief examiner. ingly divulge any inform NRC licensing examinations scheduled for I understand that I am ation about these exam

-as of the da te these licensing exam not to instruct, evaluate inations to any persons week(s) ofO_2 1 inations from this da , or provide perform (e.g., acting as a sim te until completion of ance feedback to those who have not been authorized by the ulator booth operator examination administra ap pli ca nts scheduled to be adminis feedback). Furtherm ore, I am aware of the or communicator is ac ceptable if the indivi tion, except as specifi cally noted below and tered dual does not select the authorized by the NRC understand that violat ion of the conditions of physical security mea sure tra ining the facility licensee. this agreement may res s and requirements (as documented in the fac content or provide direct or indirect I will immediately rep ort to facility manageme ult in ca nc ell ati on of the examinations an ility licensees proce may have been comprom ised. nt or the NRC chief ex aminer any indications d!or an enforcement ac dures) and tion ag or suggestions that exam ainst me or

2. Post-ExamInation ination security To the best of my know ledge , I did not divulge to during the we ek(s) of any unauthorized perso instruct, evaluate, or From the date that ns any information conc provide performance I entered into this sec erning the NRC licen below and authoriz fee db ac k to tho se applicants urity agreement unt il the completion of ex sing examinations admi nistered ed by the NRC. who were administer amination administra ed these licensing ex tion, I did not aminations, except PRINTED NAME as specifically noted JOB TITLE I RESPON SIBILITY SIGNATURE (1) i.D4in, iJkThr DATE SIGNATURE 244,iitt5 a5 44S ). DATE NOTE

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f-2w2 ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examlnatlon I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of &yO ZWZa5 of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examlnatlon To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations

, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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ES-201, Page 27 of 28

0 0 ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examlnatlon I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and!or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-ExamInation To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of . From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

C .

ES-201 Examination SeGurity Agreement Form ES-201-3

1. Pre-Examlnatlon I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 5t2° as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaLuate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and rmquirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the. NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-ExaminatIon To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing not examinations, except as specifically noted below and authorized by the NRC.

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ES-201, Page 27 of 28

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Calculate Reactor Vessel Head Venting Time Conduct of Operations DR G2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 Determine NCP Start Requirements. (2008 NRC)

Conduct of Operations DR G2.1.32, Ability to explain and apply system limits and precautions. 3.8 Develop Removal from Service for 1B Condensate Pump Equipment Control NR G2.2.13, Knowledge of tagging and clearance procedures.

4.1 / 4.3 Determine Radiation Protection Requirements for Work in SFP Demineralizer Room. (2006 NRC)

Radiation Control MR G2.3.7, Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 Emergency Procedures/Plan ---

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. NCP Seal Injection Verification Test N,S 2 003A4.01 Manually operate/monitor in the CR: Seal injection 3.3/3.2

b. Transfer to Hot Leg Recirc. A,D,EN,L,S,P 3 EA1.11 Monitor long term cooling of core for LBLOCA 4.2/4.2

c. RCCA Movement Test w/Two Dropped Rods A,N,S 1 001A4.08 Monitor mode select for CRDS and control panel 3.7/3.4

d. Verify Proper H2 Control Operation A,D,L,S 5 028A4.01 Operate/monitor HRPS controls 4.0/4.0

e. Verify Blackout Buses Energized A,N,S 6 EPE055EA1.06 Operate/monitor restoration of power 4.1/4.5

f. N/A

g. Control Tavg Using S/G PORVs in Manual A,D,S 4S 041A4.08 Operate/monitor steam dump valves 3.0/3.1

h. Place Second Train RHR (ND) in Service L,N,S 4P 005A4.01 Operate/monitor RHR pumps 3.6/3.4 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maintain S/G W/R from Aux. Shutdown Panel A,D,E,L,P 4S 061A2.04 Mitigate pump failure or improper operation 3.4/3.8

j. Break Main Condenser Vacuum Locally - Unit 2 D,E 8 045A1.06 Monitor expected response of secondary parameters following T/G trip 3.3/3.7

k. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,L,R 5 G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. NCP Seal Injection Verification Test N,S 2 003A4.01 Manually operate/monitor in the CR: Seal injection 3.3/3.2

b. Transfer to Hot Leg Recirc. A,D,EN,L,S,P 3 EA1.11 Monitor long term cooling of core for LBLOCA 4.2/4.2

c. RCCA Movement Test w/Two Dropped Rods A,N,S 1 001A4.08 Monitor mode select for CRDS and control panel 3.7/3.4

d. Verify Proper H2 Control Operation A,D,L,S 5 028A4.01 Operate/monitor HRPS controls 4.0/4.0

e. Verify Blackout Buses Energized A,N,S 6 EPE055EA1.06 Operate/monitor restoration of power 4.1/4.5

f. Initiate a VQ Release (Containment Air Release) N,S 7 029A1.03 Monitor changes in containment pressure 3.0/3.3

g. Control Tavg Using S/G PORVs in Manual A,D,S 4S 041A4.08 Operate/monitor steam dump valves 3.0/3.1

h. Place Second Train RHR (ND) in Service L,N,S 4P 005A4.01 Operate/monitor RHR pumps 3.6/3.4 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maintain S/G W/R from Aux. Shutdown Panel A,D,E,L,P 4S 061A2.04 Mitigate pump failure or improper operation 3.4/3.8

j. Break Main Condenser Vacuum Locally - Unit 2 D,E 8 045A1.06 Monitor expected response of secondary parameters following T/G trip 3.3/3.7

k. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,L,R 5 G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. N/A

b. Transfer to Hot Leg Recirc. A,D,EN,L,S,P 3 EA1.11 Monitor long term cooling of core for LBLOCA 4.2/4.2

c. N/A

d. N/A

e. Verify Blackout Buses Energized A,N,S 6 EPE055EA1.06 Operate/monitor restoration of power 4.1/4.5

f. N/A

g. N/A

h. N/A In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Maintain S/G W/R from Aux. Shutdown Panel A,D,E,L,P 4S 061A2.04 Mitigate pump failure or improper operation 3.4/3.8

j. Break Main Condenser Vacuum Locally - Unit 2 D,E 8 045A1.06 Monitor expected response of secondary parameters following T/G trip 3.3/3.7

k. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF) D,L,R 5 G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 <3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator ES-301, Page 23 of 27

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Operating Test Number: 2012-301 Initials

1. General Criteria a b*

a. The operating test conforms with the previously approved outline; changes are consistent with ,jj.

sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). v.q

b. There is no day-to-day repetition between this and other operating tests to be administered p 41 during this examination. .43

c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 .a.) 1-

d. Overlap with the written examination and between different parts of the operating test is within fjj acceptable limits. 1 vr

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

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2. Walk-Through Criteria

a. Each JPM includes the following, as applicable:

• initial conditions

• initiating cues

• references and tools, including associated procedures

• reasonable and validated time limits (average time allowed for completion) and specific desig nation if deemed to be time-critical by the facility licensee fs

• operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-.4 and a copy is attached.

Printed Name I Si nature Date

a. Author Darrell D. Hensley I t&@MG.Q_Q i&

b. Facility Reviewer(*) Chad Kidd /

c. NRC Chief Examiner (#) ti -4.e--jJ frf,

d. NRC Supervisor* L LA. t NOTE:

• The facility signature is not applicable for NRC-developed tests.

1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Catawba Nuclear Station Date of Exam: 09112 Scenario Numbers: I / 21314/ 5 Operating Test No.: 2012-301 QUALITATIVE ATTRIBUTES Initials a b*

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events. z-

3. Each event description consists of

. the point in the scenario when it is to be initiated

• the malfunction(s) that are entered to initiate the event

. the symptoms/cues that will be visible to the crew

. the expected operator actions (by shift position)

. the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

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7. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to are given.

carry out expected activities without undue time constraints. Cues

8. The simulator modeling is not altered. $f4 i5

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

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10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been aftered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position. 6 Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (58) 7 I 8 I I 718

.4L 4. s

2. Malfunctions after EOP entry (12) 2 I 2 I I 2 I

3. Abnormal events (24) 4 I 4 I 4 I.AI (

4. Major transients (12) 1 I I_I_I I I I Z 5.

6.

EOPs entered/requiring substantive actions (12) 1 I 2 I I I I I I -4 --.-

EOP contingencies requiring substantive actions (02) 0 I 0 I I I ,I

7. Criticaltasks(23) 212/2 I 2I 4

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Sept. 2012 Operating Test No.: I A E Scenarios for -

P V Scenario 1 Scenario 2 Scenario 3 Scenario 4 T M P E 0

L N CREW CREW CREW CREW T N T

A C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T R T M(*)

0 0 R T 0 R T 0 T P 0 0 P C P C 0 C P 0 C P E

R II U ROl RX NOR ILIJIi I 111 0 SRO-l 1

• S 1 11 SRO-U I/C 346 356 1 1I IIII I! 442 MAJ 7

!S 7,10 SSS 221 TS 4 s4 -.

S S S

022 R02 RX I

55 Ih: S5 IA 110 NOR SS 1 11 S

S I S SRO-I I 55555 5

S S

I/C 34 356 S

S 4 442

• tIJ s 5

N SRO-U MAJ 7 710 1 I 221 TS S

_ m1mi . Ii 022 R03 RX Ssq 5

110 NOR I

$: 1 11 SRO-l I/C 34 5 2510 ss4 II 442 SRO-U MAJ IL 7 uhF SS 8 221 TS -

S55555 iii 4 iuu 022 RO 4 RX S SSS SS I 110 SRO-l NOR ii 4W - II1. 1 11 I/C S 248 2510 442 5S SRO-U MAJ 7,10 8 11111 221 TS -

IhI1II1P 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301 -5 Facility: Catawba Date of Exam: Aug. 2012 Operating Test No.: I A E Scenarios for P V T M E Scenario I Scenario 2 Scenario 3 Scenario 4 I

CREW CREW CREW CREW C POSITION POSITION POSITION POSITION L M A T s AIB SIA B SlAB SIAIB U R T 0 R T 0 R T 0 R T 0 _Mf)_

P 1

C C 1

0 P C 1

0 P P C

1 0 RIU E

fiQ RX jjJJ ] j liii I 1 1 1 1 0 SRO-l NOR I I I iiiiuii1iii1 T 7 SRO-U I/C I I I 248 2510 j J MAJ i,io 8

+/- -

TS Ij II1 1111 0 0 2 2 RX I 111111 - I 1I 1 i i SRO-I NOR I Iiit1 ..

1111 I/C I 1jj 248 45 5 4 4 2 SRO-U MAJ i,io 6 j 3 2 2 1 TS -

- 0022 RX 110 NOR 111 I/C 442 MAJ 221 TS 022 RX 110 NOR 111 I/C 442 MAJ 221 TS 022 Instructions:

I. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Aug. 2012 Operating Test No.: I A E Scenarios for P V Scenario I Scenario 2 Scenario 3 Scenario 4 T M P E 0 I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T 0 R T 0 R T 0 R T 0 M)

T P 0 C P 0 C P 0 C P C 0 P RI U E

RO RX I IL I\1 ILrn 1 110 SRO-I1 NOR Ii i IIIIk Ib 2 1 11 SRO-U I/C 256 *45784 37 ILl 9 442 MAJ 7 7,10 1II 8 llIiI 4 221 TS IL 236 3 022 RO RX I 1 10 SROI2 NOR ii 1111 2 111 I/C 256 4578 IF. 9 442 SRO-U MAJ 7 710 11 IIL Ii 4 221 TS IL 236 IF. IN 3 022 RO RX I!b - UI Ii 1 1 10 SROI3 NOR II i I -

2 111 I/C 256 4578 iI- 37

$III 9 442 SRO-U MAJ I7t7,I0 N8 4II1 4 221 TS IF. 236 IL:F. 3 022 RO RX i 1 1 1 0 NOR i 1 2 1 1 SROI4 I/C 1111 356 235 23 8 4 4 2 SRO-U MAJ II I 7,10 8 II 6 42 2 TS - ILL 245 30 2 2 Instructions:

I. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

3. Whenever practical, both instwment and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Sept. 2012 Operating Test No.: I A E Scenarios for P V T M Scenario I Scenario 2 Scenario 3 Scenario 4 P E 0 L N T N T CREW CREW CREW CREW A

C POSITION POSITION POSITION POSITION M L

A T S A B S A B S Al B S A B U N Y R T 0 R T 0 R TI 0 R T 0 M T P E

0 C P 0 C P 0 CI P 0 C P RI U RO RX NOR III Ii: i1 I[:. hF 0 2

1 1

10 11 SRO-l III I/C 256 235 1 6 442 ill I SRO-U MAJ 8 2 221 ii 11111 TS 34 245 5 022 ILhIhhiIh .iii RO RX

• 1 0 1 10 SRO-I NOR I

IhhIII II 11$ 2 1 11 I/C I1 ii 6 442 256 235 1

SRO-U2 MAJ 8 4 111 ti: ti 2 221 TS

• I t 245 Ii 5 022 RO RX NOR I

I 11 I Idli - 1k 0 2

1 1

10 11 SRO-l IIiII Uii1Uhf I/C 256 2345 7 442 SRO-U3 MAJ TS 7

34

. II II 6 25

$II 2 4

221 022 RX I 10 NOR I/C 4 4 2 MAJ 2 2 TS 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.

3. Whenever practical, both instwment and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Catawba Date of Examination: Aug. 2012 Operating Test No.: I APPLICANTS RO X RO RO SRO-l SRO-I X SRO-l

• SRO-U SRO-U SRO-tJ X Competencies SCENARIO SCENARIO SCENARIO 12 3 4 1 2 3J4i23J4 InterpretlDiag nose Events 3456 2456 2356 2456 3456 2456 2356 2456 3456 2456 2356 2456 and Conditions 9 8 9 8 9 6 Comply With and i 1345 1678 1246 1235 1345 1678 1246 1235 1345 1678 1246 Use Procedures (1)

Operate Control 1248 2347 Boards (2) 9 10 7 Communicate and Interact ALL. ALt. ALL ALt. ALL J ALL ALL ALL ALL ALL ALL ALL I

Demonstrate Supervisory ALL ALL ALL ALL ALL ALL ALL ALL Ability (3)

Comply With and 34 235 245 25 34 235 245 25 Use Tech. Specs. (3)

Notes:

(1)lncludes Technical Specification compliance for an RO.

(2)Optional for an SRO-U.

(3)Oniy applicable to SROs.

Instwctions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

u c--

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Catawba Date of Exam: September2012 RO KIA Category Points SRO-Only Points Tier Group KKKKKKAA[AAG A2 G* Total 1 2 3 4 5 6 1 213 4

• Total

1. 1 333 33 3 18 3 3 6 Emergency &

Abnormal Plant 2 T I 1 NIA 2 1 NIA 2 9 2 2 4 Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10 1 2 2 3 3 2 3 11iI 28 2 J 3 5 t

2 iiJiioi iiJi 10 2j j 1 3 Systems Tier Totals 3 4 2 4 3 3 4 38 j 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 2 1

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ier Totals@

in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by 4 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.

7. The generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KAs.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topicsRmportance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR KI K2 K3 1<4 K5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 007EK2.02 Reactor Trip Stabilization Recovery

- - 2.6 2.8 Breakers, relays and disconnects

/1 008AK2.03 Pressurizer Vapor Space Accident I 3 2.5 2.4 E Controllers and positioners OO9EKI .01 Small Break LOCA /3 4.2 4.7 Natural circulation and cooling, including refTux boiling O11EG2.4.9 Large Break LOCA/3 3.8 4.2 Knowledge of lowpower/shutdown implications in Li accident (e.g. LOCA or loss of RHR) mitigation strategies.

OI5AKI.02 RCPMalfunctions/4 3.7 4.1 Li Consequences of an RCPS failure 022AA1-f)4 Loss of Rx Coolant Makeup / 2 3.3 3.2 DY Li Li Li Li Li Li Li Li Li Li Speed demand controller and running indicators (positive displacement pump) 025AK2.05 Loss of RHR System 14 2.6 2.6 [] [] fl [] [] Reactor building sump 029EK3.0l ATWS / 1 4.2 4.5 Li Li Li Li Li Li Li Li Li Li Verifying a reactor trip; methods 054AK1 .02 Loss of Main Feedwater /4 3.6 4.2 Li Li Li Li Li Li Li Li Li fl Effects of feedwater introduction on dry S/C 056AA1 .02 Loss of Off-site Powar / 6 4 3.9 ESF bus synchronization select switch to close bus tie breakers 057AA2.0l Loss of Vital AC Inst. Bus/6 3.7 3.8 Li Li Li Li Li Li Li Li Li Li Safety injection tank pressure and level indicators Page 1 of 2 10/3/2011 8:53AM

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7

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 062AA2.06 Loss of Nuclear Svc Water / 4 2.8 3.1 The length of time after the loss of SWS flow to a component before that component may be damaged 065AK3.04 Loss of Instrument Air 18 3 3.2 Cross-over to backup air supplies 077AG2.4.46 Generator Voltage and Electric Grid 4.2 4.2 Disturbances /6 U U U U U U U U U Ability to verify that the alarms are consistent with the plant conditions.

WEO4EK3.2 LOCA Outside Containment I 3 3.4 4.0 fl Li Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment).

05EG2.2.4 Inadequate Heat Transfer Loss of 3.4 4.7 Ability to apply technical specifications for a system.

Secondary Heat Sink / 4 Li WE1 1 EA1 .3 Loss of Emergency Coolant Recirc. / 4 3.7 4.2 Desired operating results during abnormal and emergency situations.

WE12EA2.2 Steam Line Rupture Excessive Heat

- 3.4 3.9 Adherence to appropriate procedures and operation Transfer I 4 within the limitations in the facilitys license and amendments.

Page2of2 1013/2011 8:54 AM

ES-401, REV9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003M1 .02 Dropped Control Rod I 1 3.6 3.4 Controls and components necessary to recover rod 005AK2.02 Inoperable/Stuck Control Rod I 1 2.5 2.6 LI LI LI LI LI LI Breakers, relays, disconnects and control room switches 024AK3.02 Emergency Boration / 1 4.2 LI LI LI LI LI LI LI LI LI LI Actions contained in EOP for emergency boration 032M2.04 Loss of Source Range NI / 7 3.1 LI LI LI LI LI LI LI LI LI LI Satisfactory source-range/intermediate-range overlap 033AK3.0l Loss of Intermediate Range NI 17 3.2 3.6 LI LI LI LI LI LI LI LI LI LI Termination of startup following loss of intermediate-range instrumentation O61AKI.01 ARMSystemAlarms/7 2.5 2.9 LI LI LI LI LI LI LI LI LI LI Detector limitations 067AG2.4.34 Plant Fire On-site! 8 4.2 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 076AG2.l .23 High Reactor Coolant Activity / 9 4.3 4.4 LI LI LI LI LI LI LI LI LI LI Ability to perform speciflc system and integrated plant procedures during all modes of plant operation.

WEO9EAI.2 Natural Circ./4 3.6 3.9 LI LI LI LI LI LI [ LI LI LI LI Operating behavior characteristics of the facility.

Page 1 of I 10/312011 8:57AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K4.04 Reactor Coolant Pump 2.8 3.1 fl El El fl Adequate cooling of RCP motor and seals 003K6.02 Reactor Coolant Pump 2.7 3.1 El El El El El El El El El El RCP seals and seal water supply 004K1-2&-- Chemical and Volume Control 2.7 3.2 jo El El El El El El El El El El Interface betwaen HPI flow path and excess letdown flow path 004K5.44 Chemical and Volume Control 3.2 3.4 [1 El El El El El El El El El Pressure response in PZR during in-and-out surge 005K5.01 Residual Heat Removal 2.6 2.9 El El El El El El El El El El Nil ductility transition temperature (brittle fracture) 006A4.06 Emergency Core Cooling 4.4 4.4 El [] [] ESF control panel 007A3.0l Pressurizer Relief/Quench Tank 2.7 2.9 fl El El El El El El El El El Components wtrich discharge to the PRT 01 0A3.O1 Pressurizer Pressure Control 3.0 3.2 El El El El El fl El El PRT temperature and pressure during PORV testing 010K2.01 Pressurizer Pressure Control 3.0 3.4 El I] El El [1 El El El El El El PZR heaters 012A1.01 Reactor Protection 2.9 3.4 El El El El El El El El El El Trip setpoint adjustment 013K6.01 Engineered Safety Features Actuation 2.7 3.1 El El El El El El El El El El Sensors and detectors Page 1 of 3 101312011 8:57AM

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 022A1.03 Containment Coollng 3.1 3.4 Li Li Li Li Li Li Li Containment humidity 022A2.0l ContairimentCooling 2.5 2.7 Li Li fl fl Fanmotorover-current 026A1;04 Containment Spray 3.1 3.3 Li Li Li Li Li fl Containment humidity lD3 026K4.09 Containment Spray 3.7 4.1 Li Li Li Li Li Li Li Li Li Li Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover) 039A2.04 Main and Reheat Steam 3.4 3.7 Li Li Li Li Li Li Li l Li Li Li Malfunctioning steam dump 059G2.1 .20 Main Feedwater 4.6 4.6 Li Li Li Li Li Li Li fl Li ] Ability to execute procedure steps.

059G2.2.40 Main Feedwater 3.4 4.7 Li Li Li Li Li Li Li Li Li Li Ability to apply technical specifications for a system.

061K203- Audliary/EmergencyFeedwater 4.0 3.8 Li Li Li Li Li Li Li Li Li Li AFWdieseldrivenpump L

0611(5.05 Audliary/Emergency Feedwater 2.7 3.2 Li Li Li Li Li Li Li Li Li Li Feed line voiding and water hammer 062G2.4.46 AC Electrical Distribution 4.2 4.2 Li Li Li Li Li Li Li Li Li Li Ability to verify that the alarms are consistent with the plant conditions.

063A4.01 DC Electrical Distribution 2.8 3.1 Li Li Li Li Li Li Li Li Li Li Major breakers and control powar fuses Page2of3 10/312011 8:57AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 063A4.03 DC Electrical Distribution 3.0 3.1 U U U El U El El fl Battery discharge rate 064K1.02 Emergency Diesel Generator 3.1 3.6 U DIG cooling water system 073K402 Process Radiation Monitoring 3.3 3.9 El El El El El fl El El El El Letdown isolation on high- RCS activity l

076K3.0l Service Water 3.4 3.6 U] El El U El El El U] Closed cooling water 076K3.05 Service Water 3.0 3.2 U] U] U] U] U] U] U] U] U] RHR components, contrds, sensors, indicators and alarms, including rad monitors 103K3.02 Containment 3.8 4.2 U] El U] U] U] U] U] El U] U] Loss of containment integrity under normal operations Page3of3 10/312011 8:57AM

ES-401, REV9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002K1.12 Reactor Coolant 3.5 3.6 NIS 0151<4.10 Nuclear Instrumentation 3.2 3.5 Redundant sources of information on power level LI LI 0161<5.01 Non-nuclear Instrumentation 2.7 2.8 Separation of control and protection circuits 028A2.01 Hydrogen Recombiner and Purge 3.4 3.6 Hydrogen recombiner power setting, determined by using Control fl plant data book 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems 034A4.01 Fuel Handling Equipment 3.3 3.7 fl Radiation levels 068A3.02 Liquid Radwaste 3.6 3.6 Automatic isolation 071 K3.05 Waste Gas Disposal 3:2 3.2 ARM and PRM systems 075K2.03 Circulating Water 2.6 2.7 LI LI LI LI LI fl LI LI LI LI Emergency/essential SWS pumps 079G2.2.22- Station Air 4.0 4.7 Knowledge of limiting conditions for operations and 2.2 /L/ safety limits.

Page 1 of 1 10/3/2011 8:59AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 02.1 .25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables wtiich contain performance data.

G2.1 .34 Conduct of operations 2.7 3.5 Knowledge of primary and secondary chemistry limits 02.1.37 Conduct of operations 4.3 4.6 Knowledge of procedures, guidelines or limitations associated with reactivity management G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during shutdown operations.

02.2.44 Equipment Control 4.2 4.4 fl Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions G2.3.15 Radiation Control 2.9 3.1 Knowledge of radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions 02.4.14 Emergency Procedures/Plans 3.8 4.5 Knowledge of general guidelines for EOP usage.

G2.4.2 Emergency Procedures/Plans 4.5 4.6 fl Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

02.4.21 Emergency Procedures/Plans 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions Page 1 of I 10/3/2011 8:59AM

ES-401, REV 9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 015AG2.4.46 RCP Malfunctions /4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

038EG2.4.46 Steam Gen. Tube Rupture! 3 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

054AA2.02 Loss of Main Feedwater / 4 4.1 4.4 Differentiation between loss of all MEW and trip of one MFW pump 055EA2.02 Station Blackout /6 4.4 4.6 RCS core cooling through natural circulation cooling to S!G cooling 058AG2.l.28 Loss of DC Power /6 4.1 4.1 Knowledge of the purpose and function of major system components and contrds.

077M2.07 Generator VoTtage and Electric Grid 3.6 4.0 Disturbances / 6 EDEEEDDIZL1E Operational status of engineered safety features Page 1 of 1 10/3/2011 9:00AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 1(3 K4 1(5 KS Al A2 A3 A4 G TOPIC:

RO SRO OOIAA2.04 Continuous Rod Withdrawal / 1 4.2 4.3 E D E D D Lj Reactor power and its trend 028AG2.1.30 Pressurizer Level Malfunction /2 4.4 4.0 Ability to locate and operate components, including local j 2. controls.

068AG2.4.18 ControlRoomEvac./8 3.3 4.0 Knowledge of the specific bases for EOPs.

076AA2.05 High Reactor Coolant Activity / 9 2.2 2.5 CVCS letdown flow rate indication

Page 1 of I 10/3/2011 9:03AM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 006G2.4.50 Emergency Core Cooling 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

013G2.4.2 Engineered Safety Features Actuation 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

059A24- Main Feedwater 2.9 3.4 Feeding a dry SIG J

on7 051A2.06 Auxiliary/Emergency Feedwater 2.7 3.0 Back leakage of MFW 078G2.4.8 Instrument Air 3.84.5 KnowldegeofhowAOPsareused in conjuction with EOPS Page 1 of 1 10/3/2011 9:04AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR 1(1 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 014A2.06 Rod Position Indication 2.6 3.0 E Loss of LVDT 017A2.02 In-core Temperature Monitor 3.6 4.1 Core damage 034G2.1.27 Fuel Handling 3.9 4 LI LI LI LI Knowledge of system purpose &/or Equipment function.

Page 1 of 1 10/3/2011 9:04 AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR KI K2 K3 K4 K5 KS Al A2 A3 A4 C TOPIC:

RO SRO G2.1.23 Conductof operations 2.5 3.2 El El El El El El El El El El Ability to perform specific system &

integrated plant procedures in all modes G2.1.35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs G2.2.1 Equipment Control 4.5 4.4 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.5 EquipmentControl 2.2 3.2 El El El El El El El El El El l Knowledgeoftheprocessformakingdesignoroperating changes to the facility G2.3.15 Radiation Control 2.9 3.1 El El El El El El El El El El Knowledge of radiation monitoring systems G2.3,5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.4.23 Emergency ProcedureslPlans 3.4 4.4 [] El El El El El El El El El Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

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Page 1 of 1 10/3/2011 9:05AM

ES-401-4 Record of Rejected K/As Catawba Nuclear Station Initial NRC License Exam September 2012 Tier / Randomly Reason for Rejection Group Selected K/A RO Exam 1/1 022AA1.04 Reactor coolant makeup pumps at Catawba are centrifugal RO pumps, single speed. Per instruction of Chief Examiner (Ron Aiello), replaced with 022AA1.05.

2/1 004K1.25 KA is not conducive to an operationally meaningful and valid question. Per instruction of Chief Examiner, replaced with 004K1.30.

2/1 026A1.04 KA is not conducive to an operationally meaningful and valid question. Per instruction of Chief Examiner, replaced with 026A1.03.

2/1 061K2.03 Catawba plant design does not incorporate a diesel driven AFW pump. Per instruction of Chief Examiner, replaced with 061K2.02.

2/1 073K4.02 The design of the Process Radiation Monitor for this function at Catawba makes it impossible to develop a question which would match the KA. Per instruction of Chief Examiner, replaced with 073K1.01.

2/2 079G2.2.22 There are no LCOs or safety limits associated with Station Air RO at Catawba. Per instruction of Chief Examiner, replaced with 079G2.2.44.

SRO Exam 1/2 028AG2.1.30 Topic is not conducive to an operationally valid SRO only question. Per instruction of Chief Examiner, replaced with 028G2.1.32.

2/1 059A2.04 Overlap issue with KA 054AK1.02 on the RO exam. At the instruction of the Chief Examiner this KA is being replaced with 059A2.07.

3 G2.3.5 The topic of this KA is almost identical to that of another KA on the sample plan (G2.3.15). Per instruction of Chief Examiner, replaced with G2.3.6.

7710 TRAINING CENTER 07:30:29a.m. 10022012 2 /2 ES-401 Written Examination Quality Checklist Form ES-401-6 ii rnrrçj\j Facflhly: Catawbe Nuclear Station Date of Exam: October 2, 2012 Exam Level: RO X SRO X Initial hem Deaaon a b C,

1. QuestIons and answers are technicely accurate and appflcable to the facility. cZ

2. a. NRC KIAs are referenced for all questions.

b. Faduly learning objectlvns are referenced as available..

3. SRO questions are appropriate in accordance with Section D.2.d of ES..401

4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were jppeated from thelast 2 NRC licensing exams. consuit the NRR OLprogram office).

5. Question duplication from the bcense screeningfaudit exam was controlled as indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed lndependently or L the licensee certifies that there is no duplication; or ether (explain)

6. Bank use meets nb (no more than 75 percent Bank Modified New from the banit, at least 10 percent new, and the rest newormoditled); entertheactual ROISRO- 26%136 % 9%l 12% 55% 152% NW only question distribution(s) at right.

7. Between 50 and 60 percent of the questions on Memory CIA the RO exam are written at the comprehensbn!

analysis level; the SRO exam may exceed 60 percent If the randomly selected WAs support the 5% 172% Jn 8 -ta-higher cognitive leveis; enter the actual RO I SRO quendistrlbutlon(s)atrlght.

8. References/handouts provided do not give away answers or aid In the elwnination of distractors.

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.

10. Question sychornetric quality and format meet the guidelines In Epppendoc Ø j

11. The exam contains the required number of one-point, multiple choice Items; the total is correct and agrees with the value on the cever sheet yJ 4 Printed Name! Signatu I Date a.

b.

Author Facility Revlewer()

Darrell 0. Henslev Ic)A4 Chad llod ft44k

c. NRC Chief Exeminer(#) k.Vla)

I -&/-/

6. (v4 1 V

j2

d. NRC Regional Supervisor LAALC,LLlir Note:

• The facility reviewe?s Inltialslslgnature are not applicable for NRC-develo ped examinations.

I Independent NRC reviewer Initial items In Cokain c; chief examiner concurrence requbed.

II

ES-401 Written Examination Form ES-401-9 Review Worksheet Catawba 2012-301

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

• The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

• The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

• The answer choices are a collection of unrelated true/false statements.

• One or more distractors is not credible.

• One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:

• The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

• The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

• The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

• The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6. Based on the reviewer=s judgment, is the question as written (U)nacceptable (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

7. At a minimum, explain any any ratings (e.g., how the Appendix B psychometric attributes are not being met).

RO/SRO Combined Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only Applicant could eliminate the RTA Coils (A & B) because they are not in TEST S mode so they obviously did NOT operate properly with an incoming auto TRIP signal. Reviewed 9/12/12 Looks OK.

1 H 3 X 10/01/12 Changes requested by licensee to make a one part question. Need E to add automatically to question stem. Distractor C is NOT plausible.

10/2/12 Bank question used to replace previous question with bad distractor.

S Does the new question need to say: BYB is Racked In to CONN and CLOSED. Change made SAT.

2 H 3 S 9/12/12 Looks OK.

st E 1 question asks for a mechanism for cooling. SI Flow is not a mechanism.

(Feed & Bleed?)

3 H 3 X 9/12/12 Changed to mechanism/method.

S S 10/01/12 Lowered cont. press. from 3.1 to 2.3 psig. This was the original value in r0 of the question. It was inadvertently changed. SAT E 9/12/12 1st distractor choice of 100 degrees is incorrect. Should be < 100 4 H 2 X S degrees. Change made as noted.

5 H 3 S 9/12/12 OK S 9/12/12 OK E 10/01/12 Changed seal leakoff flow from > 6 gpm to > 7.5 gpm to match AP, nd 6 F 2 X step 6 & 7. Request licensee to change 2 part to >1.1 gpm to better match enclosure 3 criteria for 8 hr SD on too high a flow from #2 seal.

10/2/12 Licensee needs to change < to > 1.1 gpm as noted above. Change S

made. SAT.

7 H 2 S 9/12/12 OK 9/12/12 OK 8 F 3 S 10/01/12 Licensee changed correct answer. Changed from IR to WR?

Question is more operational valid with the rewrite. SAT S 9/12/12 OK nd E 10/01/12 License revised question to alter correct choice for the 2 half of the question. Also reference provided shows Enclosure 9 for SG Flow restoration not Enclosure 7. The CAUTION statement in Enclosure 7 is for very high feed 9 F 3 X flow rates leading to excessive cooldown. The NOTE is for thermal shocking of the nozzle. Either answer could be argued as correct.

Recommended to change to ask, The S/G with _______ is selected to reduce the risk of ________ to S/G when reestablishing feed flow.

S 10/2/12 Changed noted as above. SAT 10 F 4 S 9/12/12 OK, Not sure about Cog Lvl rating. SAT Appears to be a direct lookup. 9/12/12 Reviewed with licensee and agreed 11 H 3 S that some interpretation is required to end up at 3.0.3 therefore it is not a direct lookup. SAT.

12 H 2 E 9/12/12 Reviewed with licensee and suggested to make just a one part

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only S question. 9/21/12 Reviewed change SAT.

E A & B not plausible. I do not believe there is a MAXIMUM time for a backup 13 F 3 X air/power supply. This is always given as a MINIMUM time.

S 9/12/12 Question modified to as for MINIMUM time.

U Possible overlap with scenario that had Zone A lockout. Question is different 14 H 3 enough from the scenario therefore; no overlap concern exits.

S 9/21/12 SAT.

E Question is vague. Change to ask why do we verify the ND valve alignments 15 L 3 X S before other ECCS alignments? 9/21/12 SAT.

9/12/12 OK E 10/01/12 Licensee requested change to eliminate all bulleted items prior to question and add Assume containment pressure in each Unit is 1.2 psig.

16 H 3 X Question now appears vague. What has B SG got to do with the intent of S the question?

nd 10/2/12 Is the 2 question to vague? What level requirement are you referring to?

S Suggest minor editorial changes so that the sentences are the same as in the procedures referenced. 9/21/12 SAT.

E 10/01/12 Licensee requested change. Distractor C does not seem very 17 F 3 X plausible now. You are asking to lower NC pressure. Why would you monitor NC temperature?

10/2/12 Changed back to originally approved question.

S Overlapped with scenario. Also A(2) not plausible. A loss of air has not affect U on position indication in the MCR.

18 F 3 X 9/12/12 Licensee will write a new question.

S 9/21/12 New question reviewed. SAT. Need distractor analysis completed.

E 9/12/12 Question (2) enhanced by stating IAW Rod Retrieval Procedure and S correctly identifying the Rod Control Alarm Reset pushbutton.

9/21/12 Reviewed changes. SAT.

19 H 3 X U st 10/01/12 Licensee requested change. NOTE: The 1 part WILL is answered nd by the wording of the 2 question. Question is UNSAT now.

E nd 10/2/12 Change wording for 2 part to say Whenever a ROD CONTROL is S received, . Change made. SAT.

20 H 3 S 9/12/12 OK 21 H 3 S 9/12/12 OK S 9/12/12 OK 22 H 3 E 10/1/12 Reactor Licensing Tasks Licensee requested change.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only S 10/2/12 Changes supported operationally valid NI readings. SAT S 9/12/12 OK 23 H 3 X E 10/01/12 Licensee requested change. Request that licensee rewrite to make S a one part question just based on T.S. timeline actions.

10/2/12 Changes made as noted above. SAT.

S 9/12/12 OK E 10/01/12 Licensee requested change. Agree with licensee comment. Why 24 H 3 X nd not make the new 2 half question a one part question. Use radiation reading S from MSL monitor or offgas monitor.

10/2/12 Changes made as noted above. SAT.

25 F 3 S 9/12/12 OK E D not plausible. The normal position of the valve is DEMIN. Also verify that 26 F 3 X distractor C can not be used to answer another question.

S 9/21/12 Changed D distractor from Place to Ensure. SAT Requested licensee to verify what parameters are provided at the SSF to E

match provided readings for NC.

27 H 2 X S 9/21/12 NC System Press removed as it is not needed to answer question.

SAT 28 F 3 S 9/12/12 OK E Bold #2 seal to match the bold on #1 seal.

29 H 2 S 10/01/12 SAT E Changed C(2) and D(2) to Reduce the degassing time to match procedure 30 H 3 S wording. 9/21/12 Reviewed changes made. SAT 31 H 2 S 9/12/12 OK 32 H 3 S 9/12/12 OK 33 H 3 S 9/12/12 OK E Requested modification of valve description on choice C & D to include their 34 F 3 relationship with the PRT. i.e RMW to PRT Spray S 9/21/12 Reviewed changes. SAT 35 H 3 S 9/12/12 OK A & B distractors would be more plausible if another 600 v load center was E

listed instead of 120v. NOTE: LP OP-CN-LP-AD states pwer supply as SLXG 36 H 2 X which feeds SMXG. This may potentially confuse the applicant.

S 9/12/12 Changes incorporated.

U If you block the IR Hi Flux Trip in part 1 of the answer response, how can a 37 H 3 X high flux IR trip exist as a possible choice for the answer in part 2?

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only S 9/19/12 Licensee agreed and removed IR from 2 nd part of answer. SAT E Requested C & D include the word BOTH prior to Train A to clarify choice.

38 H 3 9/21/12 Reviewed changes. SAT S 10/01/12 Licensee requested change. Minor terminology change, agreed. SAT Wording in distractors did not match procedure. The word SELECT should E

be changed to START or PLACE. Also, remove humidity values from the 39 F 3 stem as it is not needed.

S 9/21/12 Reviewed changes. SAT nd E Add Low Speed to 2 bullet for LCVU operation. Also add the word 40 F 3 Elevated to C(2) & D(2).

S 9/21/12 Changes Reviewed. SAT.

41 F 2 S 9/19/12 OK 42 F 4 S 9/19/12 OK 9/19/12 OK 43 H 3 S 10/01/12 Licensee requested change. One unnecessary bullet in stem removed. I agree. SAT.

44 F 3 S 9/19/12 OK S 9/19/12 OK E 10/01/12 Licensee requested change. Should state: What are the MODES of 45 F 3 applicability.?

S 10/2/12 Changes noted as above. SAT 46 H 3 S 9/19/12 OK U Overlap with SRO #89. Question #89 revised to exclude overlap.

47 H 3 S 9/21/12 Verified no more overlap w/ Q#89. SAT.

The alarm would come in for either a loss of one or both coolers. C could be E argued as a correct answer also. Need to clarify that based on the condition 48 H 4 X given, BOTH (1) AND (2) will occur together.

S 9/19/12 Agreed that only one fan could be running based on given conditions.

SAT 9/19/12 OK 49 H 2 S 10/01/12 Licensee requested change. Streamlines distractor choices. Agree.

SAT 50 F 2 S 9/19/12 OK E Requested slight wording change to clarify question. Change distractor A 51 H 3 wording to match other distractors; i.e. The D/G can ONLY receive Add

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only the word BOTH to distractor D.

S 9/21/12 Reviewed changes. SAT.

52 F 3 S 9/19/12 OK 53 F 3 S 9/19/12 OK A & B not plausible because the direction to OPEN the valve would cause temperature to increase further vs. lowering temperature. A(1) and B(1) does U not match how the valve operates. Change wording to say modulates in the CLOSED direction. Replace A(2) & D(2) with OAC alarm instead to remove the 1AD-10 alarm reference for a HI-Hi temp to match the OAC type alarm E received for distractors B & D.

54 H 3 X 9/21/12 Reviewed changes. SAT S

10/01/12 Licensee requested change. A2 & C2 not plausible. If the HX outlet opens to lower temp, why would the bypass also open? Change A2 & C2 to S require manual operator action to CLOSE 10/2/12 Changes made as noted above. SAT Requested a rewrite of this question due to the low plausibility of distractor D.

E Sent the license a rewrite that improves the LOD and plausibility.

55 F 2 X 9/21/12 Reviewed new question. SAT.

S 10/01/12 Licensee requested change. Minor editorial change. Agree. SAT st 1 question is confusing. Change to read What is the FINAL alignment of the E following components?

56 F 3 9/21/12 Reviewed changes. SAT.

S 10/01/12 Licensee requested change. Agreed to add VCT Outlet Switch in NORMAL. SAT 57 H 3 S 9/19/12 OK 58 F 3 S 9/19/12 OK 59 H 3 S 9/19/12 OK E Question is really related to when SFPT increases to 200 degrees F. Change 60 H 3 to ask When is the FIRST time.

S 9/21/12 Reviewed changes. SAT.

E The EMF-39 rad monitor is labeled incorrectly. It is the Containment GAS 61 F 3 Monitor vs. Containment Particulate Monitor.

S 9/21/12 Reviewed changes. SAT.

E Need to add bullet to clarify that the alarm could not be cleared w/i 60 seconds as stated by the ARP.

62 F 3 S 9/21/12 Reviewed changes. SAT.

st E 10/01/12 Licensee requested change. Change wording of 1 question to the

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only nd release is terminated. Remove the word immediately from the 2 question.

Not relevant.

S 10/2/12 Changes made as noted above. SAT.

E In distractor B change 0EMF-50L (Waste Gas Disch - Low Range) to 0EMF-63 H 3 X 41. This will make B plausible.

S 9/21/12 Reviewed changes. SAT.

E D not plausible. Change to NEITHER Train A Pumps start.

64 H 3 X S 9/21/12 Reviewed changes. SAT.

E Not plausible? Why would a loss of SA cause a loss of IA? Licensee explained that the SA crosstie could be open at times. Requested the 65 H 3 X question be changed to have the cross-tie open as an initial condition.

S 9/21/12 Reviewed changes. SAT.

66 H 3 S 9/19/12 OK nd 1st question is answered by the 2 question.

Licensee changed question from Dissolved Oxygen to Fluoride to made U

secondary plant more plausible.

E 67 F 3 X 9/21/12 Reviewed changes. SAT.

10/01/12 Licensee requested change. Why does an RO have to know the 3 hr S

SD criteria?

10/2/12 Agreed to changes noted. SAT.

9/19/12 OK 68 F 2 S st 10/01/12 Licensee requested change. Note: periods at the end of the 1 two bullets but not the last two bullets. Otherwise OK. SAT 9/19/12 OK 69 F 3 S 10/01/12 Licensee requested change. I agree with the plants assessment of the original question. New question written. SAT U Does not meet KA.

70 H 3 X S 9/25/12 New Question written to meet the KA. SAT.

71 F 3 S 9/19/12 OK 72 H 2 S 9/19/12 OK 73 H 3 S 9/19/12 OK 74 F 2 S 9/19/12 OK 75 H 3 S 9/19/12 OK SRO

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only H 3 X E C not plausible. Stby MU Pump cannot be non-functional and the SSF be 76 functional.

S 9/25/12 Question rewritten to eliminate non-plausibility. SAT th 77 E Remove 6 bullet. No input is needed to infer that all equipment responded H 4 X as expected. No other issues at this time.

S 9/10/12 OK H 3 E Minor editorial remarks. Remove BOTH from distractor A, not needed.

78 S 9/21/12 Reviewed changes. SAT.

H 3 X E The stem of the question informs you that want to stay in NC mode. Why 79 would you leave a procedure that tells you that you are in NC mode to go to one that is not designated for NC mode?

S 9/10/12 Accepted question as is after discussion with licensee.

F 3 X E Remove Vital from distractor B & D. The stem leads to the correct distractor 80 otherwise. Licensee removed vital from the stem instead.

S Reviewed changes. SAT.

81 E Based on the information given, it appears that B is the correct answer?

H 3 S 9/10/12 Reviewed w/ licensee. SAT E 9/10/12 Discussed revising to make only one part question with UE, Alert, 82 H 3 S SAE, or GE as options. 9/21/12 Reviewed changes. SAT.

83 E 9/10/12 Discussed revising to change stratification to equalization.

H 2 S 9/21/12 Reviewed changes. SAT.

84 E 9/10/12 Discussed removal of Case II info from the stem to make distractor A H 3 more plausible.

S 9/21/12 Reviewed changes made. SAT.

85 E 9/10/12 Discussed rearranging question order to be more logical.

H 3 S 9/21/12 Reviewed changes. SAT.

86 H 3 S 9/10/12 SAT 87 F 3 S 9/10/12 SAT 88 U Does not meet KA.

X 9/9/12 NEW KA Assigned 059A2.07 S 9/21/12 Replacement question reviewed. SAT.

U Overlaps with Q#47.

89 H 2 9/21/12 Enclosure provides guidance on the cooling CA piping to remove E conditions favorable to gas formation in CA pump and its discharge path.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#/ LOK LOD (F/H) (1- Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO U/E/S Explanation

5) Focus Dist. Link units ward K/A Only Suggest change responses to: prevent gas formation upstream or downstream of discharge check valve.

9/25/12 Editorial comment incorporated. SAT 90 U Does not meet KA.

H 3 X S 9/21/12 Reviewed changes. SAT 91 F 3 S 9/10/12 SAT.

92 E TSC not staffed makes C2 not plausible and 700 degrees is a subset of 1200 degrees.

H 3 9/10/12 Subset issue resolved. Need to review final question.

S 9/21/12 Reviewed changes. SAT.

E 9/10/12 Requested licensee to verify that B2 & D2 portion is not also correct.

93 F 3 X Change the end of the distractors B2 & D2 to not exceeded vs. are met S 9/21/12 Changed B2 & D2 distractor. Reviewed changes. SAT.

E 9/10/12 Requested licensee to change to a one part question using just 94 H 3 nd different times. Omit the 2 question.

S 9/21/12 Reviewed changes. SAT.

You can remove (if any) since you dont have a choice with no additional 95 E requirements needed. Change to say What additional MINIMUM requirement(s) must be met Change A & C to say the Refueling SRO must be present in the Rx Bldg.

F 2 9/10/12 Requested minor editorial corrections. Remove ONLY from distractor A. Distractor C & D should both be maintained or restored but not both.

S 9/21/12 Reviewed changes. SAT.

H 3 S 9/10/12 SAT 96 Appears to be OK. Need to look at their 50.59 procedure to verify.

97 F 3 S 9/10/12 SAT F 3 S 9/10/12 SAT 98 Choice A. Is this referring to the Shared Equipment Return Header for the 99 E Monitor Tank Bldg discharge? If so, shouldnt it be stated as such to match the information in the LP? Other than the referenced OP, which tells you to H 4 stop the release, I could not locate information that states why you cannot continue a release in this lineup. Is this considered an unmonitored release?

S 9/10/12 SAT 100 H 3 S 9/10/12 SAT

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: C_cV cW.S\3 Date of Exam: ( )I Exam Level: RO1 SROfl Initials Item Description a b c

1. Clean answer sheets copied before grading

2. Answer key changes and question deletions justified and_documented

3. Applicants scores checked for addition errors A (reviewers_spot_check>_25%_of examinations)

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail -

5. All other failing examinations checked to ensure that grades ...E\1A_

are justified

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity I 3 L -

of questions_missed_by_half or_more of the_applicants Printed Name!Signature Date

a. Grader bcJ.rftl

b. Facility Reviewer(*) tt /.-,c2i

c. NRC Chief Examiner (*) G I

d. NRC Supervisor (*) LLLU T

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Q W..k)\3 & Date of Exam: Z0(5 i( Exam Level: ROfl SRO[1 Initials Item Description a b c

1. Clean answer sheets copied before grading 6J

2. Answer key changes and question deletions justified and documented IcL1 j:Z +)tL

3. Applicants scores checked for addition errors (reviewers_spot_check>_25%_of examinations) p

4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail

5. All other failing examinations checked to ensure that grades are justified 4kS1 /

6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity pjj._.

of questions_missed_by_half or more of the_applicants Printed Name/Signature Date

a. Grader lO r

4 r aSlfML

b. Facility Reviewer(*) 4II /,%

c. NRC Chief Examiner (*) /&t

d. NRC Supervisor (*) .

(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-403, Page 6 of 6

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Catawba Nuclear Station Date of Exam: 09/12 Scenario Numbers: 1 / 2 / 3 Operating Test No.: 2012-301 QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events.

3. Each event description consists of

• the point in the scenario when it is to be initiated

• the malfunction(s) that are entered to initiate the event

• the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

• the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

7. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

8. The simulator modeling is not altered.

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Total malfunctions (5-8) 7 / 8 / 7

2. Malfunctions after EOP entry (1-2) 2 / 2 / 2

3. Abnormal events (2-4) 4 / 4 / 5

4. Major transients (1-2) 1 / 1 / 1

5. EOPs entered/requiring substantive actions (1-2) 1 / 2 / 1

6. EOP contingencies requiring substantive actions (0-2) 0 / 0 / 1

7. Critical tasks (2-3) 2 / 4 / 2

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine if Shift Manning Requirements are Met.

Conduct of Operations MR G2.1.5, Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. 3.9 Determine NCP Start Requirements. (2008 NRC).

Conduct of Operations MR G2.1.32, Ability to explain and apply system limits and precautions. 4.0 Develop Removal from Service for 1B Condensate Pump Equipment Control NR G2.2.13, Knowledge of tagging and clearance procedures.

4.1 / 4.3 Determine Radiation Protection Requirements for Work in SFP Demineralizer Room. (2006 NRC)

Radiation Control MR G2.3.7, Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.6 Upgrade an Emergency Classification and Complete an Emergency Notification Form.

Emergency Procedures/Plan DR G2.4.41, Knowledge of the emergency action level thresholds and classifications. 4.6 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Sept. 2012 Operating Test No.: 1 A E Scenarios - for P V Scenario 1 Scenario 2 Scenario 3 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO 1 RX --- 1 1 1 1 0 SRO-I NOR 1 --- 1 1 1 1 I/C 346 2510 7 4 4 2 SRO-U MAJ 7 8 2 2 2 1 TS --- --- 0 0 2 2 RO 2 RX --- 1 1 1 1 0 NOR 1 --- 1 1 1 1 SRO-I 1 I/C 346 2510 7 4 4 2 SRO-U MAJ 7 8 2 2 2 1 TS --- --- 0 0 2 2 RO 3 RX --- 1 1 1 1 0 NOR 1 --- 1 1 1 1 SRO-I I/C 346 458 6 4 4 2 SRO-U MAJ 7 7 2 2 2 1 TS --- --- 0 0 2 2 RO 4 RX --- 1 1 1 1 0 NOR 1 --- 1 1 1 1 SRO-I I/C 37 458 5 4 4 2 SRO-U MAJ 8 7 2 2 2 1 TS --- --- 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Aug. 2012 Operating Test No.: 1 A E Scenarios - for P V Scenario 1 Scenario 2 Scenario 3 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO 5 RX 1 1 2 1 1 0 SRO-I NOR --- --- 1 1 1 1 I/C 2510 458 7 4 4 2 SRO-U MAJ 8 7 2 2 2 1 TS --- --- 0 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Aug. 2012 Operating Test No.: 1 A E Scenarios - for P V Scenario 1 Scenario 2 Scenario 3 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO RX 1 --- --- 1 1 1 0 SRO-I 1 NOR --- 1 1 2 1 1 1 I/C 256 235 2369 10 4 4 2 SRO-U MAJ 7 8 7 3 2 2 1 TS --- 245 --- 3 0 2 2 RO RX 1 --- --- 1 1 1 0 NOR --- 1 1 2 1 1 1 SRO-I 2 I/C 256 235 456 9 4 4 2 SRO-U MAJ 7 8 7 3 2 2 1 TS --- 245 23 5 0 2 2 RO RX 1 --- --- 1 1 1 0 NOR --- 1 1 2 1 1 1 SRO-I 3 I/C 256 235 2369 10 4 4 2 SRO-U MAJ 7 8 7 3 2 2 1 TS --- 245 --- 3 0 2 2 RO RX 1 --- 1 1 1 0 NOR --- 1 1 1 1 1 SRO-I 4 I/C 2510 456 7 4 4 2 SRO-U MAJ 8 7 2 2 2 1 TS --- 23 2 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Catawba Date of Exam: Sept. 2012 Operating Test No.: 1 A E Scenarios - for P V Scenario 1 Scenario 2 Scenario 3 T M P E O I L N CREW CREW CREW CREW T N I T A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T O R T O R T O R T O M(*)

T P O C P O C P O C P O C P R I U E

RO RX --- --- 0 1 1 0 SRO-I NOR 1 1 2 1 1 1 I/C 256 37 5 4 4 2 SRO-U 1 MAJ 7 8 2 2 2 1 TS 34 --- 2 0 2 2 RO RX --- --- 0 1 1 0 NOR 1 1 2 1 1 1 SRO-I I/C 256 2369 7 4 4 2 SRO-U 2 MAJ 7 7 2 2 2 1 TS 34 --- 2 0 2 2 RO RX --- --- 0 1 1 0 NOR 1 1 2 1 1 1 SRO-I I/C 256 456 6 4 4 2 SRO-U 3 MAJ 7 7 2 2 2 1 TS 34 23 4 0 2 2 RX 1 1 0 NOR 1 1 1 I/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.